ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
H. Takenaga, H. Kawashima, S. Nishio, K. Tobita
Fusion Science and Technology | Volume 57 | Number 1 | January 2010 | Pages 94-102
Technical Paper | doi.org/10.13182/FST10-A9270
Articles are hosted by Taylor and Francis Online.
A fueling scenario in a fusion reactor has been investigated, where tritium is fueled in the main plasma and deuterium is fueled in both the main plasma and the edge plasma. The tritium fueling in the main plasma minimizes the tritium fueling rate necessary for sustaining the high tritium density in the main plasma, resulting in the minimum tritium recycling level at the fixed pumping fraction. The deuterium fueling in the main plasma sustains the high deuterium density in the main plasma, and the deuterium fueling in the edge plasma enhances the deuterium recycling level for reducing the divertor temperature. Based on this scenario, particle balance was quantitatively investigated using the SlimCS design parameters at 2.95-GW fusion output with consideration of confinement times separately estimated for the particles fueled in the main plasma and the edge plasma. The fueling rates in the main plasma were evaluated to be 2.5 × 1022/s for tritium and 1.4 × 1022/s for deuterium when the confinement times for the particles fueled in the main and edge plasmas were assumed to be 2 s and 2 ms, respectively, and the divertor pumping fraction was assumed to be 3% of the particle flux to the divertor plates. For enhancement of the recycling level, the additional deuterium fueling in the edge plasma of 3.6 × 1023/s was required in this case. In order to satisfy the tritium balance, it was necessary to suppress the tritium retention rate to <0.01% of the tritium recycling rate and the tritium loss in the tritium cycle system to below 0.2% of the tritium fueling rate with the tritium breeding ratio of 1.05.